Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Investigation of Hydraulic Characteristics of Loops with Lead Coolant

12/10/2025 2025 - #04 Thermal physics and thermal hydraulics

Sumin R.V. Zyryanova T.K. Bokova T.A. Volkov N.S. Pogorelov M.D. Shalina D.S. Kolosov S.V.

DOI: https://doi.org/10.26583/npe.2025.4.05

UDC: 621.039.5

The article is devoted to an experimental study of the hydraulic characteristics of lead coolant circulation routes. The aim of the study is to obtain calculation formulas for determining hydraulic losses in the elements of a circulation circuit, such as friction losses in a straight pipe and local resistances (smooth turns, sharp narrowing), as well as comparing experimental data with existing recommendations. The experience of operating experimental stands with lead and lead-bismuth coolant shows that this class of coolant has a number of properties that have a significant effect on the fluid dynamics of the coolant. In the course of an experimental study, a significant discrepancy was found between the data obtained and recommendations from the literature. Calculation formulas for determining the hydraulic losses in the elements of the circulation circuit are also obtained. The friction losses along the length of the straight pipe and smooth turns for the lead coolant are significantly higher than recommended. At the same time, pressure losses at a sharp constriction can be considered to coincide with the recommendations. The results of the study are proposed for use in the development of circulation circuits of reactor installations with lead coolant of the BREST and BR-1200 types, experimental stands and in the verification of design codes.

References

  1. Adamov E.O., Kaplienko A.V., Orlov V.V., Smirnov V.S., Lopatkin A.V., Lemekhov V.V., Moiseev A.V. Brest Lead-Cooled Fast Reactor: From Concept to Technological Implementation. Atomic Energy. 2021;129(4):179–187. DOI: https://doi.org/10.1007/s10512-021-00731-w
  2. Handbook of Russian Nuclear Power. Closed Nuclear Fuel Cycle with Fast Reactors (general edit. prof. E.O. Adamov). Moscow, NIKIET Publ., 2020, 502 p. ISBN 978-5-98706-129-9 (in Russian).
  3. Beznosov A.V., Dragunov Yu.G., Rachkov V.I. Heavy liquid metal heat carriers in nuclear power engineering. Moscow, IzdAT, 2007, 432 p. ISBN 5-86656-202-2 (in Russian).
  4. Park H., Choi C.-H., Kim C.-J. Superhydrophobic drag reduction in turbulent flows: a critical review. Experiments in Fluids. 2021;62(229):1–29. DOI: https://doi.org/10.1007/s00348-021-03322-4
  5. Beznosov A.V., Bocova T.A., Drozdov Yu.N., Makhov K.A., Novozhilova O.O., Yarmonov M.V. Tribological characteristics of the contact zones a coolants of nuclear fast reactors nuclear power plant. Proceedings of the Samara Scientific Center of the Russian Academy of Sciences. 2011;13(4–3):676–680 URL: https://elibrary.ru/item.asp?id=17933949 (accessed Nov. 10, 2025). EDN: MBYYCD (in Russian).
  6. Gose J.W., Golovin K., Boban M., Mabry J.M., Tuteja A., Perlin M., Ceccio S.L. Characterization of superhydrophobic surfaces for drag reduction in turbulent flow. Journal of Fluid Mechanics. 2018;845:560–580. DOI: https://doi.org/10.1017/jfm.2018.210
  7. Ma W., Karbojian A., Sehgal B.R., Dinh T.-N. Thermal-hydraulic performance of heavy liquid metal in straight-tube and U-tube heat exchangers. Nuclear Engineering and Design. 2009;239(7):1323–1330. DOI: https://doi.org/10.1016/j.nucengdes.2009.03.014
  8. Idelchik I.E. Handbook of hydraulic resistance (edit. M.O. Steinberg). Moscow, Mashinostroenie Publ., 1992, 672 p. ISBN 5-217-00393-6 (in Russian).
  9. Yablokov A.M., Kozhukhov Yu.V., Sadovsky N.I. Numerical study of the effect of equivalent sand roughness of an impeller on the characteristics of a low-flow stage of a centrifugal compressor. Bulletin of the International Academy of Refrigeration. 2020;4:3–11. DOI: https://doi.org/10.17586/1606-4313-2020-19-4-3-11
  10. Safety Manual “Design ratios and methods for calculating the hydrodynamic and thermal characteristics of elements and equipment of nuclear power plants with liquid metal coolant” (RB-075-12). Federal Environmental, Technological and Nuclear Supervision Service, Moscow, 2012 (Effective from August 31, 2012) (in Russian).

lead coolant fast neutron reactor hydrodynamics hydraulic resistances

Link for citing the article: Sumin R.V., Zyryanova T.K., Bokova T.A., Volkov N.S., Pogorelov M.D., Shalina D.S., Kolosov S.V. Investigation of Hydraulic Characteristics of Loops with Lead Coolant. Izvestiya vuzov. Yadernaya Energetika. 2025, no. 4, pp. 66-79; DOI: https://doi.org/10.26583/npe.2025.4.05 (in Russian).